Author: Armin F. LietzkePublisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 52
Book Description
Simplified Analysis of Nuclear Fuel Pin Swelling
Author: Armin F. LietzkePublisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 52
Book Description
Nuclear Science Abstracts
Author: Uranium Resource Processing
Author: Chiranjib GuptaPublisher: Springer Science & Business Media
ISBN: 9783540679660
Category : Science
Languages : en
Pages : 550
Book Description
The book emphasizes various aspects of processing secondary sources for recovery of uranium. The field of secondary resource processing is gaining ground over the last few years as it is eco-friendly, economical and in tune with the philosophy of sustainable development. The book is the first one of its type in the area and includes a succint and comprehensive description of related areas of ore mineralogy, resource classification, processing principles involved in uranium solubilisation followed by separation and safety aspects. The clear organisation and the carefully selected figures and tables makes the treatment invaluable for practising engineers, research workers and academic institutions.
U Uranium
Author: Publisher: Springer Science & Business Media
ISBN: 3662060140
Category : Science
Languages : en
Pages : 371
Book Description
The present volume A4 of the "Uranium" series of the Gmelin Handbook deals with two very important technological aspects of the nuclear fuel cycle: - the behavior of fuel elements during burnup in a nuclear reactor, and - the reprocessing of spent fuel to recover the non-fissioned uranium and newly created materials. The usefullifetime of a fuel element in a nuclear reactor depends strongly on the change of its chemical and physical properties during irradiation. Properties like thermal conductivity, swelling, creep, and oxygen-to-metal ratio are strongly affected by the intense neutron field and the energetic fission products. Furthermore, the high temperature gradient in a fuel element also produces alterations of the initial fuel. such as densification or U: Pu segregation. All of these effects are thoroughly discussed for the different kinds of fuels to be used in modern nuclear reactors today or in the future. The vast amount of very often Contradietory results in sometimes difficultly obtainable Iiterature has been summarized to create a compendium in this field with the two sections, on oxide and on carbide and nitride fuels, respectively. The chapters on reprocessing of spent fuels deal only with fuel elements of the uranium 235 thorium fuel cycle and with those containing fuel highly enriched in U. The treatment of U0 2 and (U,Pu)0 has already been given in the transuranic element series.
Fundamental Nuclear Energy Research
Author: U.S. Atomic Energy Commission. Division of Plans and ReportsPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 988
Book Description
Reactor Materials
Author: Nuclear Science Abstracts
Author: Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors
Author: International Atomic Energy AgencyPublisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 100
Book Description
The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
ERDA Authorizing Legislation, Fiscal Year 1977: On uranium enrichment; environmental research and safety ... [etc
Author: United States. Congress. Joint Committee on Atomic EnergyPublisher:
ISBN:
Category :
Languages : en
Pages : 724
Book Description
ERDA Authorizing Legislation, Fiscal Year 1977: Uranium enrichment; environmental research and safety; laser fusion; magnetic fusion; fuel cycle R. & D.; nuclear materials security and safeguards; high energy physics; and basic energy sciences held February 17, and March 11, 17, 18, and 19, 1976
Author: United States. Congress. Joint Committee on Atomic EnergyPublisher:
ISBN:
Category :
Languages : en
Pages : 732
Book Description